15
Views
5
CrossRef citations to date
0
Altmetric
Modeling and Simulations

A Neutronic Evaluation of Reprocess Fuel and Depletion Study of VHTR Using MCNPX and WIMSD5 Code

, , , , &
Pages 338-342 | Published online: 10 Aug 2017

References

  • A. B. ALAJO, P. V. TSVETKOV; “Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTRs” Annals of Nuclear Energy 38 p.88–97 (2011)
  • P. V. TSVETKOV, T. G. LEWIS III, A. B. ALAJO, D. E. AMES II; “Used fuel vectors and waste minimization strategies for VHTRS operating without refueling” Nuclear Engineering and Design 240 p.2458–2465 (2010)
  • G. F. VANDEGRIFT,, et al. Lab-scale demonstration of the UREX+ process, in Proc. 4th WM Conference. Tucson, p.1-10.
  • D. WARIN, Future nuclear fuel cycles: prospect and challenges for actinide recycling, Materials Science and Engineering 9 012063, doi:10.1088/1757-899X/9/1/012063(2010)
  • Y. KIM, C. CHO and F. VENNERI; “Long-Cycle and High-Burnup Fuel Assembly for the VHTR” Journal of NUCLEAR SCIENCE and TECHNOLOGY 44 No. 3, p.294–302 (2007)
  • J. R. ASKEW, F. J. FAYERS, F. B. KEMSHELL, “A General Description of the Lattice Code WIMS,” Journ. of the Brit. Nucl. En. Soc. 5 p.564 (1966)
  • F. LESZCZYNSKI, “Metodos y usos Del código WIMSD4”, Comision Nacional de Energia Atômica – Centro Atômico Bariloche, (1990)
  • J. F. BRIESMEISTER, “MCNP, A General Monte Carlo N-Particule Transport Code”, Version 4C, Los Alamos National Laboratory, Report LA- 13709-M (2000)
  • J. S. HENDRICKS, et al. MCNPX 2.6.0 Manual Extensions, Los Alamos National Laboratory, Report LA-UR-08-2216 (2008).
  • P. V. TSVETKOV, T. G. LEWIS III, A. B. ALAJO, D. E. AMES; “VHTR-based systems for autonomous co-generation applications” II Nuclear Engineering and Design 240, p.2451–2457 (2010)
  • X.W. ZHOU, C.H. TANG; “Current status and future development of coated fuel particles for high temperature gas-cooled reactors” Progress in Nuclear Energy 53, p. 182-188 (2011)
  • D. M. SCATES, J. K. HARTWELL, J. B. WALTER, M. W. DRIGERT, J. M. HARP; “Fission product monitoring of TRISO coated fuel for the advanced gas reactor-1 experiment” Nuclear Engineering and Design 240 p.2493–2499 (2010)
  • G. D. del CUI, et al. “TRISO-Coated Fuel Processing to Support High-Temperature Gas-Cooled”, OAK RIDGE NATIONAL LABORATORY- ORNL/TM-2002/156–(2002)
  • DOE-HTGR-90406 “MHTGR nuclear physics benchmarks” General Atomics
  • A. TALAMO, Doctoral Thesis, “Advanced in-core fuel cycles for the gas turbine–modular helium reactor,” Royal Institute of Technology /KTH, Department of Nuclear and Reactor Physics, Stockholm (2006)
  • E. ARNDT, R. FICHER, “Design status of the HTR 500 power plant and the HTR module power plant” IAEA Technical Committee Meeting on GCR Technology (1989)
  • S. D. S. COTA, Estudo neutrônico preliminar da reciclagem de combustíveis alternatvos em reatores PWR”, Dissertação do Departamento de Engenharia Nuclear, UFMG (1996).
  • C. PEREIRA et al., Results from Current Studies of Simulations in Nuclear Power Systems Performe d by the Department of Nuclear Engineering of the Federal University of Minas Gerais’, Brazil”, 14th International Conference on Emerging Nuclear Energy Systems- ICENES- Ericeira, Portugal, (2009)
  • C. S. FABIANO, “Reatores Avançados de Alta Temperatura: Avaliação neutrônica preliminar utilizando os códigos WIMSD e MCNP”. Dissertação de Mestrado em Engenharia Nuclear. Universidade Federal de Minas Gerais, UFMG, Brasil, (2008)
  • T. A. TAIWO and R. N. HILL, Summary ofGeneration-IV Transmutation Impacts: ANL-AFCI-150, Nuclear Engineering Division, Argonne National Laboratory (2005)
  • M. LABAR, et al; “Status of the DB-MHR for electricity production”, WNA Symposium (2003)
  • C. A. M. da SILVA et al., Application of Nuclear Codes WIMSD-5B and MCNPX 2.6.0 to a Qualittive Evaluation of MHR (Modular Helium Reactor, in 8th International Conference on Mathematical Problems in Engineering, Aerospace and Sciences, São José dos Campos, Brazil, June 30- July 3, 2010.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.